ML11222A114
| ML11222A114 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/08/2011 |
| From: | Berg M WorleyParsons Ltd |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WBNAPS3127, Rev 0 | |
| Download: ML11222A114 (14) | |
Text
Enclosure 1 TVA Letter Dated August 4, 2011 Responses to Licensee Open Items to be Resolved for SER Approval TVA Calculation WBNAPS3127, "EQ Dose in the Control Building," Revision 0
LEGIBIL1TY EVALUATED AND ACCEPTED FOR ISSUE.AL*E,-S SIGNATURE Rtv 6 DATE Page I
ISdw pow.s WSH4APS3-127 B IJ I
ACTMO I ONE a DELETE I]
SUPERSEOE E3 0
REMMtE 0]ArUPUCATE OCRIS UPDATE ONLY 0 (Verifier Approval Signatues Not
-(For ýcal revisin. CCFOS OW rvwdad i
ibis clculafion deemined dwe EQ&doe in the Control Huling. WBNTSR-1 12 determiled the 100-dayT.OCA EQ dosa usng the radioisotope concwtratios at the =ontrol oomIntake (either WestINormal or Euxt/Eniergency). The pressurization air for the rooms of interst is taken from the WestlNormal intake. This cWculadton modified the WBNTSR-112 doses to correct, for the West/Normal intake.
The cootma dose was based on an asswumed I wmvfte since there are normally no sources in the roms.
The resubk of the calculation were grad&]:
E1.753 Mecbanical El.755 All Othe ADl Othe Control Building:
- SLquimem Roai*
Room Evmios (EL6853, 729, and 708) 40 Year Oama Normal 350.4 350.4 350A 100-Day Gamma Accident 710.5 4.632 66.T GamM Total (Normal +
.AccideM) 1060.9 355.03...
4_17.1.
100-Day Beta Accidct 95A 7.73 95.4 Gamma + Beta Total.
o
+Accidet) 1156.3 362.76 5.12.
.*=
-Iins is we Hr.,A iage lace, wtnc ist me largest dogem in, room -For lcations odler than the HIt A large face, tdo dose w
NPG CALCULATION COVERSHEETICCRIS UPDATE Page 2
lAL C. IrD TYPF '
OPR IPLANT IRPANCII NI IMRI:
I PFVX V# l*V I*
P1 ANT BRANCH
- age ITCN I
NUC ILWBLN IONTB IFWBNATS3127
- 000 ALTERNATE CALCULATION IDENTIFICATION
- BLDG ROOM ELEV COORD/AZIM FIRM Print Report Yes [
NA NA NA NA Polestar CATEGORIES : NA KEY NOUNS (A-add, D-delete)
ACTION KEY NOUN A/D KEY NOUN (A/D)
A EQ CROSS-REFERENCES (A-add, C-change, D-delete)
ACTION XREF XREF XREF XREF XREF XREF-(/C/D)
CODE TYPE PLANT BRANCH NUMBER REV A
NTB WBNNAL3025 A
_______G9,14-NT-B--
E~~3O 414 6 Z
rI A
P CO GEN NTB FENCDOSE A
P DW WBN NTB 47W200-6 CCRIS ONLY UPDATES:
Following are required only when making keyword/cross reference CCRIS updates and page 1 of form NEDP-2-1 is not included:
'PREPARER SIGNATURE DATE CHECKER SIGNATURE DATE PREPARER PHONE NO.
EDMS ACCESSION NO.
TVA 40532 [10-2008]
Page 2 of 2 NEDP-2-1 [10-20-20081
Page 3 NPG CALCULATION RECORD OF REVISION CALCULATION IDENTIFIER WBNAPS3-127 Title EQ Dose in the Control Building Revision DESCRIPTION OF REVISION No.
0 Initial Issue. WBNAPS4-004 and WBNOSG4-004 will become successors to this calculation
'and should be revised to reflect the results.-
RO: 13 total pages TVA 40709 [10-2008]
Page 1 of 1 NEDP-2-2 110-20-20081
Page 4
NPG CALCULATION TABLE OF CONTENTS Calculation Identifier: WBNAPS3-127 I Revision: 0 TABLE OF CONTENTS SECTION TITLE PAGE Coversheet I
Revision Log 2
Calculation Design Verification Form 3
Table of Contents 4
Calculation Verification Form 5
Computer Input File Storage Information Sheet 6
Computer Output Microfiche Information Sheet 7
Purpose 8
Introduction 8
Assumptions 8
Special Requirements/Limiting Conditions 8
Calculations 9
Results 13 References 13 WA 40710 110-2008)
Page 1 of I NEDP-2-3 El 0-20-2008)
TVA 40710 [10-20081 Page I of I NEDP-2-3 [10-20-20081
Page 5 NPG CALCULATION VERIFICATION FORM Calculation Identifier WBNAPS3-127 Revision 0 Method of verification used:
- 1.
Design Review 0
- 2.
Alternate Calculation El Verifier.
. -,ate
- 3.
Qualification Test Comments:
I have reviewed WBNAPS3-127 and have found the calculation to have been completed in a technically sound and appropriate manner for the scenario specified in the text. In conducting the verification, I reviewed the methodology, design input, and assumptions, which I have found to be valid and conservative.
I ITVIAIII Il 40331-208 "g 1 of1N"
-2I
[1-0-08 TVA 40533 [10-2008)
Pawl1 of I NEDP-2-4 [10-20-20081
Page 6
NPG COMPUTER INPUT FILE STORAGE INFORMATION SHEET Document WBNAPS3-127 Rev. 0 Plant: WBN
Subject:
EQ Dose in the Control Building
[
Electronic storage of the input files for this calculation is not required. Comments:
There are no computer runs associated with this calculation L
Input files for this calculation have been stored electronically and sufficient identifying information is provided below for each input file. (Any retrieved file requires re-verification of its contents before use.)
El Microfiche/eFiche WA 4535[10-008 Pag 1 f 1NEOP2-6[1 020-008 TVA 40535 (10-2008]
Page 1 of 1 NEDP-2-6 [10-20-20081
NPG COMPUTER OUTPUT page 7 MICROFICHE INFORMATION SHEET Document WBNAPS3-127 Rev. 0 Plant: WBN
Subject:
EQ Dose in the Control Building Microfiche Number Description There are no computer runs associated with this calculation
Calculation No.
WBNAPS3-127 Rev: 0 Plant: WBN Page: 8
Subject:
EQ Dose in the Control Building Prepared: MCB Date:
Checked: JEB Date:
Purpose The purpose of this calculation is to determine the total EQ dose (100-day accident plus 40-year normal dose) in the Control Building.
Introduction This calculation is to establish an EQ dose of<IE3 rads for the Control Building. Additionally, the dose in the E1.755 Mechanical Equipment Room (where the control room filters are located) is also performed.
Assumptions
- 1. It is assumed that the normal operation dose rate in the Control Building has a I mrem/hr background dose rate.-
Technical Justification: References I and 2 have documented no normal radiation source in the Control Building. The assumed value of 1 mrem/hr is the customary and reasonable assumed value for such rooms. Also, this is the value at which RADCON considers an area to be a general access area. See also assumption #2.
- 2. In all Control Building Rooms the dose due to the Control Building Emergency filters may be neglected, except for the room where the filters are located (E1.755 Mechanical Equipment Room):
Technical Justification: The Control Building Emergency Filers will be contaminated during a LOCA (ref.3). The largest dose in the E1.755 room is on the HEPA large face (705.9 rads). However, once one gets a distance from the filters, the doses drop dramatically. For instance, in the control room proper (through a cinder block wall), the doses drop to <5E-4 rads. It can be concluded that doses due to the filters may be ignored due to intervening floor/ceilings plus the distance involved.
- 3. Tle air in the Control Building that is not in the Control Room Habitability Zone may be assumed to be the same as that found at the west end (normal) intake of the control building.
Technical Justification: From ref. 4, the outside air that is used to pressurize the Control Building excluding the Control Room Habitability Zone during both normal and post Control Room Isolation (CRI) modes is normally aligned to the Control Building air intake located on the West end of the building (the "normal control room intake"). The flow rate is not specified on the flow diagram, but the balancing damper associated with this flow path was set in order to achieve a pressure that is a minimum of 1/8 inch w.g. less than the MCR during a CRI in order to maintain a positive pressure in the MCR. Since there is a positive flow of air into the rooms from the intake, the concentrations in the room may be assumed to be same as that at the intake. Also, any inleakage will come from the control room habitability zone (same intake, and is also filtered), or from adjacent buildings. Air from adjacent buildings, such as the Turbine Building, will have had greater dilution than the intake location due to greater distance and circuitous travel path to get to those locations.
Special Requirements/Limiting Conditions There are no special requirements or limiting conditions in this calculation
Calculation No.
WBNAPS3-127 Rev: 0 Plant: WBN Page: 9
Subject:
EQ Dose in the Control Building Prepared: MCB Date:
Checked: JEB Date:
Calculations 40-Year Normal Gamma Dose Since there are no identified normal operation sources in these rooms (ref. 1 and 2), it is assumed that the background dose rate is I mrem/hr. The 40-year normal operating dose is therefore:
I mrem/hr
- 1 rad/rem
- 24 hr/day
- 365 days/yr
- 40 yr / (1000 mrem/rem) = 350.4 rads 100-day Accident Gamma Dose For Rooms in the Control Room Habitability Zone the contaminated air is filtered. The 100-day airborne gamma dose was determined in WBNTSR-005 (ref.3) as 4.632 rads. In the Mechanical Equipment Room the filter shine dose was determined to be an additional 705.9 rads (HEPA large face),
For Control Building rooms not in the Control Room Habitability Zone the air is not filtered, therefore the doses will be different. From ref. 4, the outside air that is used to pressurize the Control Building during both normal and post Control Room Isolation (CRT) modes is normally aligned to the Control Building air intake located on the West end of the building.
The flow rate is not specified on the flow diagram, but the balancing damper associated with this flow path was set in order to achieve a pressure on the elevations that is a minimum of 1/8 inch w.g. less than the MCR during a CRT.
The doses due the activities at the intake were determined in WBNTSR-1 12 (ref.5) which in turn were derived from LOCA releases from TI-RPS-198 (ref.7). These dose rates were determined using the worst case X/Q values for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, then the more favorable intake X/Q after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Since the more favorable intake is not the normal (West) intake, the dose rates must be modified by the ratio of the X/Q values.
From WBNTSR-104:
LOCA X/Q [sec/cum]
Air intake 2 hr 2-8 hr 8-24 hr 1-4 day 4-30 days No/location Unit I Case No. 1 Full Rx Bldg 4.47E-04 2.81E-04 1.21E-04 9.36E-05 7.77E-05 1/East Unit 1 Case No. 2 Full Rx Bldg 1.09E-03 9.50E-04 4.56E-04 3.09E-04 2.35E-04 2NVest 1/2 Rx Bldg 1.09E-03 9.59E-04 4.60E-04 3.09E-04 2.37E-04 2/Vest 1/4 Rx Bldg 1,09E-03 9.72E-04 4.65E-04 3.10E-04 2.39E-04 2NVest 1/8 Rx Bldg 1.12E-03 9.78E-04 4.73E-04 3.10E-04 2.41 E-04 2/West No Bldg Area 1.29E-03 1.16E-03 5.55E-04 3.35E-04 2.64E-04 2/West Unit 2 Case No. 3 Full Rx Bldg 8.28E-04 7.69E-04 3.90E-04 2.98E-04 2.17E-04 1/East 1/2 Rx Bldg 8.28E-04 7.75E-04 3.94E-04 2.99E-04 2.18E-04 1/East 1/4 Rx Bldg 8.63E-04 7.69E-04 4.01E-04 2.99E-04 2.19E-04 1/East 1/8 Rx Bldg 8.85E-04 7.73E-04 4.09E-04 3.OOE-04 2.21E-04 1/East No Bldg Area 9.78E-04 9.08E-04 4.71E-04 3.21E-04 2.36E-04 1/East Unit 2 Case No. 4 Full Rx Bldg 4.13E-04 3.54E-04 1.90E-04 1.43E-04 1.03E-04 2/West TI-RPS-198/WBNTSR-1 12 X/Q values [sec/cum] used were:
0-2 hr 2-8 hr 8-24 hr 1-4 day 4-30 days 1.12E-03 9.78E-04 1.21E-04 9.36E-05 7.77E-05 Worst case X/Q (unit I case 2 vs. unit 2 case 4, 1/8 Rx. Bldg) 0-2 hr 2-8 hr 8-24 hr 1-4 day 4-30 days case 2 U1 to West
- 1. 12E-03 9.78E-04 4.73E-04 3.1OE-04 2.41E-04 case 4 U2 to West 4.13E-04 3.54E-04 1.90E-04 1.43E-04 1.03E-04 Worst Case:
1.12E-03 9.78E-04 4.73E-04 3.1OE-04 2.41E-04
Calculation No.
WBNAPS3-127 Rev: 0 Plant: WBN Page: 10
Subject:
EQ Dose in the Control Building Prepared: MCB Date:
Checked: JEB Date:
Correction Ratio:
The correction ratio is the worst case X/Q divided by the X/Q used by WBNTSR-112:
0-2 hr 2-8 hr 8-24 hr 1-4 day 4-30 days WBNTSR-112 X/Q 1.12E-03 9.78E-04 1.21E-04 9.36E-05 7.77E-05 Correction X/Q L.00E+00 1.OOE+00 3.91E+00 3.31E+00 3.10E+00 Taking the WBNTSR-1 12 results and correcting them using the correct (West) intake X/Q results in the following: (note, the 720-2400 hr X/Q values are assumed to the be same as the 96-720 hr X/Q):
Gamma Dose [rads] in Rooms not in Control Room Habitability Zone 0-2 hr 2-8 hr 8-24 hr 24-96 hr 96-720 hr 720-2400 hr correction ratio 1.OOOE+00 1.OOOE+00 3.909E+00 3.312E+00 3.102E+00 3.102E+00 WBNTSR-1 12 Dose 8.965E+00 9.818E+00 7.646E+00 4.144E+00 1.336E+00 5.799E-02 Total over 100 days 32.0 Corrected Total 8.965E+00 9.818E+00 2.989E+01 1.372E+01 4.144E+00 1.799E-01 Total over 100 days 66.7 I 00-day Accident Beta Dose For Control Building Rooms not in the Control Room Habitability Zone, the beta dose is determined the same as that in ref.3.
From TI-RPS-198 (ref.7) COROD run R198C23A (UI PCO control loop single failure, conventional core) which produced the highest beta dose:
4-30 day dose rate: 3.785 mrads/hr 30 day continuous occupancy dose: 1.371E3 mrads30-100 day dose: 3.785 mrad/hr
- 24 hr/day
- 70 day = 6.3588E3 mrads total 100-day airborne+shine dose: 1.371E3 + 6.3588E3 = 7.73E3 mrads = 7.73 rads The activity at the control room intake vent is also used to determine the beta dose rate for the control building rooms. The average intake concentrations are taken from WBNTSR-112. The formulas for determining the average beta dose rate from a semi-infinite cloud for each isotope is (ref.9):
Dbeta =0.23E(X/Q)(Q/AT)
- 3600 sec/hr where D= dose rate from a semi-infinite cloud [rem/hr]
E=average gamma or beta energy for the isotope per disintegration [MeV/dis]
X/Q=Dispersion Coefficient [sec/cum]
Q/AT=integrated concentration of isotope over time interval AT [Ci/sec]
(X/Q)(Q/AT) = [Ci/cum] as determined by COROD, found in WBNTSR-1 12 (note: these concentrations are based on X/Q values that must be corrected, see gamma correction above)
The total dose rate is the summation of all dose rates from each isotope. The average energy of each isotope is taken from ref. 10.
Calculation No.
WBNAPS3-127 IRev: 0 Plant: WBN Page: I
Subject:
EQ Dose in the Control Building Prepared: MCB Date:
Checked: JEB Date:
From WBNTSR-1 12:
Concentration (C) at Control Room Intake (Ci/m3)*
Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138, Xe-139 Xe-140 1-130 1-131 1-132 1-133 1-134 1-135 Im-136 1-130*
1-131
- I1-32*
1-133*
1-134*
1-135*
Im-136*
0-2 hr 1.774E-04 4.669E-04 2.404E-05 6.211E-04 1.173E-03 5.382E-05 0.OOOE+00 2.436E-05 1.416E-04 4.440E-03 4.622E-04 1.508E-03 0.000E+00 4.389E-04 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.175E-05 7.032E-05 1.059E-04 9.952E-05 9.926E-05 0.OOOE+00 0.OOOE+00 2.965E-06 3.889E-06 6.043E-06 5.235E-06 5.615E-06 0.000E+00 2-8 hr 4.591E-05 2.537E-04 2.385E-05 9.650E-05 4.583E-04 7.828E-17 0.OOOE+00 2.400E-05 1.345E-04 4.333E-03 6.035E-04 1.313E-03 0.000E+00 4.706E-07 0.OOOE+00 0.000E+00 0.0OOE+00 2.626E-06 9.8 1OE-07 4.681E-06 2.64 l E-07 3.171 E-06 0.OOOE+00 0.OOOE+00 3.266E-07 1.218E-07 5.816E-07 3.256E-08 3.94 1E-07 0.OOOE+00 8-24 hr 1.577E-06 4.442E-05 1.926E-05
- 1. 103 E-06 3.802E-05 0.000E+00 0.OOOE+00 1.903E-05 9.603E-05 3.333E-03 3.207E-04 6.133E-04 0.OOOE+00 3.319E-15 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.283E-06 3.571 E-08 1.665E-06 4.422E-10 5.609E-07 0.OOOE+00 0.000E+00 1.598E-07 4.448E-09 2.073E-07 5.485E-11 6.99 1E-08 0.OOOE+00 24-96 hr 5.294E-10 4.570E-07 7.115E-06 2.481E-I1 8.9711E-08 0.OOOE+00 0.000E+00 6.636E-06 2.256E-05 1.0 14E-03 1.788E-05 3.499E-05 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.890E-07 1.904E-I1 1.273E-07 1.132E-16 7.92 1E-09 0.000E+00 0.OOOE+00 3.601E-08 2.372E-12 1.585E-08 1.403E-17 9.872E-10 0.000E+00 96-720 hr 2.094E-23 1.418E-13 1.543E-06 8.012E-32 3.430E-17 0.OOOE+00 0.000E+00 8.031 E-07 3.706E-07 5.139E-05 5.93 1E-10 3.824E-09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 2.406E-08 1.402E-22 3.472E-10 0.OOOE+00 1.098E-13 0.OOOE+00 O.OOOE+00 2.998E-09 1.746E-23 4.324E-I I 0.000E+00 1.367E-14 0.OOOE+00 720-2400 hr 0.000E+00 0.000E+00 1.442E-06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.385E-08 9.385E-08 6.376E-07 0.OOOE+00 8.453E-31 0.OOOE+00 0.OOOE+00 0.0OOE+00 0.OOOE+00 0.OOOE+00 1.029E-09 0.OOOE+00 1.161E-19 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.282E-10 0.OOOE+00 1.446E-20 0.OOOE+00 0.OOOE+00 0.OOOE+00
Calculation No.
WBNAPS3-127
Subject:
EQ Dose in the Control Building Beta Doses in Rooms not in Control Room Habitability Zone Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Xe-139 Xe-140 1-130 1-131 1-132 1-133 1-134 1-135, Im-136 1-130*
1-131*
1-132*
1-133" 1-134*
1-135*
Im-136*
Aver. Beta Energy (E)
MeV DeltaT 3.708E-02 2.529E-01 2.506E-0 I 1.324E+00 3.750E-01 1.23 1E+00 1.197E+00 I.428E-01 1.898E-01 1.354E-01 9.500E-02 3.168E-01 1.642E+00 6.058E-0 I 1.835E+00 1.1 17E+00 2.802E-0 I 1.943E-01 5.143E-01 4.080E-01 6.102E-01 3.680E-01 2.21 OE+00 2.802E-01 1.943E-01 5.143E-01 4.080E-01 6.102E-01 3.680E-0 I 2.210E+00 0-2 hr 2
1.089E-02 1.955E-01 9.976E-03 1.361E+00 7.284E-0 I 1.097E-01 0.OOOE+00 5.761 E-03 4.45 IE-02 9.955E-0 1 7.27 IE-02 7.911 E-01 0.OOOE+00 4.403E-01 0.OOOE+00 0.OOOE+00 0.000E+00 1.665E-02 5.989E-02 7.155E-02 1.006E-01 6.049E-02 0.OOOE-00 0.OOOE+00 9.540E-04 3.312E-03 4.083E-03 5.290E-03 3.422E-03 0.000E+00 5.092E+00 1.OOOE+00 5.092E+00 2-8 hr 6
8.457E-03 3.188E-01 2.969E-02 6.346E-0 I 8.53 8E-0 I 4.787E-13 0.OOOE+00 1.703E-02 1.268E-0 I 2.915E+00 2.848E-0 I 2.066E+00 0.000E+00 1.416E-03 0.OOOE+00 0.OOOE+00 0.000E+00 2.535E-03 2.506E-03 9.488E-03 8.006E-04 5.797E-03 0.000E+00 0.OOOE4-00 3.153E-04 3.112E-04 1.179E-03 9.870E-05 7.205E-04 0.000E+00 7.280E+00 1.000E+00 7.280E+00 (rem/hr) 8-24 hr 16 7.747E-04 1.488E-01 6.394E-02 1.934E-02 1.889E-01 0.OOOE+00 0.OOOE+00 3.600E-02 2.415E-01 5.979E+00 4.036E-01 2.574E+00 0.000E--00 2.664E-I1 0.000E+00 0.000E+00 0.000E+00 3.303E-03 2.433E-04 9.OOE-03 3.575E-06 2.735E-03 0.OOOE+00 0.OOOE+00 4.113E-04 3.03 1 E-05 1.120E-03 4.434E-07 3.408E-04 0.OOOE+00 9.673E+00 3.909E+00 3.781E+01 24-96 hr 72
- 1. 1 70E-06 6.890E-03 1.063E-01 1.958E-06 2.006E-03 0.OOOE+00 0.OOOE+00 5.649E-02 2.553E-01 8.185E+00 1.013E-01 6.608E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.348E-03 5.838E-07 3.096E-03 4.118E-12 i.738E-04 0.000E+00 0.OOOE+00 4.171E-04 7.273E-08 3.855E-04 5.104E-13 2.166E-05 O.OOOE+00 9.382E+00 3.312E+00 3.107E+-0I 96-720 hr 624 4.012E-19 1.853E-08 1.998E-01 5.480E-26 6.646E-12 0.OOOE+00 0.OOOE+00 5.925E-02 3.634E-02 3.595E+00 2.911 E-05 6.259E-04 0.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 2.415E-03 3.725E-17 7.319E-05 0.000E+00 2.088E-08 O.OOOE+00 0.OOOE+00 3.01 OE-04 4.640E-18 9.115E-06 O.OOOE+00 2.599E-09 0.OOOE+00 3.894E+00 3.102E+00 1.208E+01 total 30-100 day 1680 0.OOOE+00 0.OOOE+00 5.027E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.864E-02.
2.478E-02 1.201E-01 0.OOOE+00 3.725E-25 0.OOOE+00 O.000E+00 0,000E+00 0.OOOE+00 0.000E+00 2.781E-04 0.000E+00 6.589E-14 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.465E-05 0.OOOE+00 8.207E-15 0.OOOE+00 0.OOOE+00 0.OOOE+00 total X/Q correction ratio corrected total 6.665E-0 1 3.102E+00 2.067E+00 9.540E+O I
Calculation No.
WBNAPS3-127 Rev: 0 Plant: WBN Page: 13
Subject:
EQ Dose in the Control Building Prepared: MCB Date:
Checked: JEB Date:
Results The total doses [rads] were determined to be:
E1.755 Mechanical EI.755 All All Other Control Equipment Room*
Other Rooms Building Elevations (E1.685.5, 729, and 708) 40 Year Gamma 350.4 350:4 350.4 Normal 100-Day Gamma Accident 710.5 4.632 66.7 Gamma Total (Normal + Accident) 1060.9 355.03 417.1 100-Day Beta Accident 95.4 7.73 95.4 Gamma + Beta Total (Normal + Accident) 1156.3 362.76 512.5
- This is the HEPA large face, which is the largest dose in the room. For locations other than the HEPA large face, the dose will be less depending on location (see WBNTSR-005).
Discussion and Conclusion All rooms in the Control Building, except the E1.755 Mechanical Equipment Room, have doses <1 E3 rads.
References
- 1. WBNNAL3-0 18 R2 "Auxiliary Building Piping Source Term Data"
- 2. WBNNAL3-025 R6 "Normal Operation Dose For Equipment Qualification Outside the Shield Building"
- 3. WBNTSR-005 R4 "Dose due to the Control Building Emergency Air Cleanup Filters"
- 4. WBN CCD drawing 1-47W866-4 R39
- 5. WBNTSR-1 12 R6 "Shield Design Review and Equipment Qualification Study"
- 6. WBNAPS3-104 R2 "WBN Control Room X/Q"
- 7. TI-RPS-198 R23 "Dose to Control Room Personnel Due to a Regulatory Guide 1.4 Loss of Coolant Accident"
- 9. Computer Code FENCDOSE R3, code ID 262358, controlled user's manual #8
- 10. GENAPS3-018 RI "NEB Isotope Library Verification"